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130208e19640612dcu ot f0|||||eng|d |
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|a (TOE)ost10178135
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|a (TOE)10178135
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|a TOE
|c TOE
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|a GDWR
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|a 11
|2 edbsc
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|a 37
|2 edbsc
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|a E 1.99:hw--82896
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|a E 1.99:hw--82896
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| 088 |
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|a hw--82896
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| 245 |
0 |
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|a Fission product ratios of the Purex filter
|h [electronic resource]
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| 260 |
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|a Washington, D.C. :
|b United States. Dept. of Energy ;
|a Oak Ridge, Tenn. :
|b distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy,
|c 1964.
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| 300 |
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|a 22 p. :
|b digital, PDF file.
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| 336 |
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|a text
|b txt
|2 rdacontent.
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| 337 |
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|a computer
|b c
|2 rdamedia.
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| 338 |
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|a online resource
|b cr
|2 rdacarrier.
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| 500 |
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|a Published through the Information Bridge: DOE Scientific and Technical Information.
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| 500 |
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|a 06/12/1964.
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| 500 |
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|a "hw--82896"
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| 500 |
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|a "DE94017844"
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| 500 |
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|a Weiler, M.R.
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| 513 |
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|a Topical;
|b 06/01/1964.
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| 520 |
3 |
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|a This report details measurements of fission product ratios which were made an various samples of the Purex canyon exhaust filter to determine the manner and time interval in which the filter became plugged vith foreign material. Results for samples from different levels within the filter bed were compared to investigate accumulation as a function of depth. Strontium-89/strontium-90, Zr-95/Ca-137, Ru-103/Ru-106, and Ce-141/Ce. Pr-144, ratios were determined. These were compared to a constant rate model for accumulation of fission products on the filter. Observed Sr-89/Sr-90 and Zr-95/Cs-137 ratios fall within a range of values typical of normal plant operation, Specifically long-term accumulation of Hanford material irradiated at 10 MW/T to between 600 and 900 MWD/T total exposure and cooled between 120 and 200 days. Low Ru-103/Ru-106 and Ce-141/Ce, Pr-144 ratios definitely rule out rapid accumulation of short-cooled material as the build-up mechanism but are not sensitive indicators in the case of long-cooled material. Ratios did not vary significantly with sample location, indicating that accumulation age does not differ with depth within the filter.
|
| 536 |
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|b AC06-76RL01830.
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| 650 |
|
7 |
|a Ruthenium 106.
|2 local.
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| 650 |
|
7 |
|a Radiochemical Analysis.
|2 local.
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| 650 |
|
7 |
|a Strontium 89.
|2 local.
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| 650 |
|
7 |
|a Filters.
|2 local.
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| 650 |
|
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|a Concentration Ratio.
|2 local.
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| 650 |
|
7 |
|a Purex Process.
|2 local.
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| 650 |
|
7 |
|a Promethium 144.
|2 local.
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| 650 |
|
7 |
|a Ruthenium 103.
|2 local.
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| 650 |
|
7 |
|a Cesium 137.
|2 local.
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| 650 |
|
7 |
|a Sampling.
|2 local.
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| 650 |
|
7 |
|a Cesium 141.
|2 local.
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| 650 |
|
7 |
|a Strontium 90.
|2 local.
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| 650 |
|
7 |
|a Zirconium 95.
|2 local.
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| 650 |
|
7 |
|a Fission Products.
|2 local.
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| 650 |
|
7 |
|a Nuclear Fuel Cycle And Fuel Materials.
|2 edbsc.
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| 650 |
|
7 |
|a Inorganic, Organic, Physical And Analytical Chemistry.
|2 edbsc.
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| 710 |
2 |
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|a Hanford Atomic Products Operation.
|4 res.
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| 710 |
1 |
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|a United States.
|b Department of Energy.
|4 spn.
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| 710 |
2 |
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|a Hanford Site (Wash.).
|4 res.
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| 710 |
1 |
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|a United States.
|b Department of Energy.
|b Office of Scientific and Technical Information.
|4 dst.
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| 856 |
4 |
0 |
|u http://www.osti.gov/servlets/purl/10178135-0drjVk/native/
|z Online Access
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| 907 |
|
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|a .b73007298
|b 03-07-23
|c 02-08-13
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| 998 |
|
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|a web
|b 02-08-13
|c f
|d m
|e p
|f eng
|g dcu
|h 0
|i 1
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| 956 |
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|a Information bridge
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| 999 |
f |
f |
|i 412119e5-9b81-57d6-9a4a-5eaa83f2e23f
|s 2c78dbf8-4465-531f-be73-2918eafb5f29
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| 952 |
f |
f |
|p Can circulate
|a University of Colorado Boulder
|b Online
|c Online
|d Online
|e E 1.99:hw--82896
|h Superintendent of Documents classification
|i web
|n 1
|
